Text

Proposed Operating Test - Dynamic Simulator Scenarios
	ML20252A251
Person / Time
Site:	Prairie Island
Issue date:	08/27/2020
From:	; Nuclear Management Co
To:	; NRC/RGN-III/DRS/OLB
	Callaway G
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ML19127A304	List: ML20245E566; ML20245E574; ML20245E576; ML20245E579; ML20245E580; ML20252A248; ML20252A251; ML20252A254;
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Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.: 1 Op-Test No.: PI-ILT-NRC-2001S Examiners: Gary Calloway Operators: Shift Supervisor (SS)

Joe DeMarshall Balance of Plant (LRO)

Dave Lanyi At the Controls (RO)

Initial Conditions:

Reactor Power: 1x10-8 AMPS Equipment OOS: NONE Boron Concentration: 1575 PPM RCS temperature: 549°F Other: B/U PRZR heaters are ON RCS pressure: 2235 PSIG Two 40 GPM orifices are in service Xenon: Free prior to S/U Rods: CBD @ 142 STEPS Main Generator: 0 MW Turnover:

Secure the 11 TD AFW Pump Raise reactor power to the point of adding heat (POAH)

Event Malf. Event Type* Event No. No. Description 1 N (BOP) SECURE 11 TD AUXILIARY FEEDWATER PUMP R (ATC) 2 RAISE POWER TO THE POAH N (SRO) 3 C (ATC) 12 CHARGING PUMP TRIP C (BOP) 4 11 TD AFWP ACCUMULATOR LOW AIR PRESSURE TS (SRO) 5 TS (SRO) 11 CTMT VACUUM BREAKER FAILS CLOSED 6 M (ALL) FAULTED 12 SG TO CONTAINMENT 7 C (ATC, SRO) 12 MD AFW PUMP FAILS TO AUTO START 8 C (BOP, SRO) SI TO FEEDWATER/CONDENSATE RELAY FAILURE

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.: 2 Op-Test No.: PI-ILT-NRC-2002S Examiners: Gary Calloway Operators: Shift Supervisor (SS)

Joe DeMarshall Balance of Plant (LRO)

Dave Lanyi At the Controls (RO)

Initial Conditions:

Reactor Power: 100% Equipment OOS: 11 TD AFW Pump Boron Concentration: 102 PPM RCS temperature: 560°F Other:

RCS pressure: 2235 PSIG Xenon: Equilibrium Rods: CBD @ 218 STEPS Main Generator: 582 MW Turnover:

Swap running EH Oil Pumps Event Malf. Event Type* Event No. No. Description 1 N (BOP) SWAP RUNNING EH OIL PUMPS I (ATC) 2 CONTROLLING PRZR PRESS CH FAILS LOW TS (SRO) 3 TS (SRO) D1 LOCAL ALARM 4 C (BOP) TURBINE EH VALVE MALFUNCTION R (ATC) 5 RAPID DOWNPOWER TO 50%

N (SRO) 6 M (ALL) LOSS OF ALL AC 7 C (BOP) TURBINE FAILS TO AUTO TRIP 8 C (BOP, SRO) D2 FAILS TO AUTO START 9 C (ATC, SRO) 12 MD AFW PUMP FAILS TO AUTO START

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: PRAIRIE ISLAND Scenario No.: 3 Op-Test No.: PI-ILT-NRC-2003S Examiners: Gary Calloway Operators: Shift Supervisor (SS)

Joe DeMarshall Balance of Plant (LRO)

Dave Lanyi At the Controls (RO)

Initial Conditions:

Reactor Power: 60% Equipment OOS: 11 SI Pump Boron Concentration: 230 PPM RCS temperature: 554°F Other:

RCS pressure: 2235 PSIG Xenon: Equilibrium Rods: CBD @ 178 STEPS Main Generator: 338 MW Turnover:

Swap running RMU pumps Event Malf. Event Type* Event No. No. Description 1 N (BOP) SWAP RMU PUMPS I (ATC) 2 1ST STAGE PRESSURE INSTRUMENT FAILS LOW TS (SRO)

R (ATC) 3 RESTORE TAVG TO TREF N (SRO)

I (ATC, BOP) 4 PRZR LEVEL INTERLOCK CHANNEL FAILS LOW TS (SRO) 5 M (ALL) 11 STEAM GENERATOR TUBE RUPTURE 6 C (BOP, SRO) 11 & 12 RHR PUMPS FAIL TO START AUTOMATICALLY 7 C (BOP, SRO) SI TO COOLING WATER RELAY SIGNAL FAILURE

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Rev. 0 (12/14/2018) Page 1 of 28 SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # PI-ILT-NRC-2001S SEG TITLE: 2020 ILT NRC SIMULATOR EVALUATION #1 REV. # 0 PROGRAM: LICENSE REQUALIFICATION TRAINING #: FL-ILT COURSE: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT TOTAL TIME: 1.5 HOURS Developed by: Fredrick Collins Instructor Date Reviewed by: Justin Hasner Instructor Date (Simulator Scenario Development Checklist.)

Validated by: Fredrick Collins Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 2 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Guide Requirements Evaluation Evaluate the crews ability to:

Objectives:

1. Secure 11 TDAFW Pump IAW 1C28.1.

2. Raise Reactor Power to the POAH IAW 1C1.2-M2.

Evaluate the crews ability to diagnose and respond to:

3. 12 Charging Pump Trip IAW C47015.

4. 11 TDAFW Pump Accumulator Low Air Pressure IAW C47010.

5. 11 CTMT Vacuum Breaker failing closed IAW C47021.

6. 12 Steam Generator Faulted to Containment IAW 1E-2.

7. 12 MDAFW Pump Fails to Auto Start on SI IAW 1E-0.

8. SI to Feedwater/Condensate Relay Failure IAW 1E-0 Att. L.

Training 1. Full Scope Simulator Resources: 2. Operations Management Representative

3. Evaluation Team

4. Booth Operator (Backup Communicator)

5. Primary Communicator Related PRA Initiating Event with Core Damage Frequency:

Information: NONE Important Components:

12 MDAFW PMP 11 TDAFW PMP Important Operator Actions with Task Number:

CRO 301 003 06 01 000 - Faulted Steam Generator Isolation Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 3 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Secure 11 TDAFW Pump

2. Raise Reactor Power to the POAH

3. 12 Charging Pump Trip

4. 11 TDAFW Pump Accumulator Low Air Pressure

5. 11 CTMT Vacuum Breaker Fails Closed After EOP Entry:

1. SI to Feedwater/Condensate Relay Failure

2. 12 MDAFW Pump Fails to Auto Start Abnormal Events:

1. 12 Charging pump trip

2. 11 TDAFW Pump Accumulator Low Air Pressure

3. CTMT vacuum breaker failure Major Transients:

1. 12 Steam Generator Faulted to Containment Critical Tasks:

PI-CT-10B: Establish feed water flow to the INTACT Steam Generator to prevent the INTACT Steam Generator from reaching DRYOUT conditions.

PI-CT-19: Stop feed flow to the faulted Steam Generator within 45 minutes of this critical tasks plant conditions being met.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 4 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 CRITICAL TASK SHEET Number: PI-CT-10B Critical Task: Establish feed water flow to the INTACT Steam Generator to prevent the INTACT Steam Generator from reaching DRYOUT conditions.

Safety With insufficient feed water flow, the Steam Generators dry out, causing an RCS pressure increase Significance: that opens the pressurizer PORVs. The open PORVs create a small break LOCA that challenges the Core Cooling CSF. Failure to maintain an adequate heat sink will result in degradation of the Fuel Clad Barrier and RCS Barrier.

Plant Conditions:

One faulted steam generator.

At least one SG is required for heat sink.

Feed water flow is available but not established from any of the following:

o Auxiliary Feed Water Pumps o Main Feed Water Pumps o Condensate Pumps

Sufficient time is available to align feed water flow to at least one Steam Generator prior to Wide Range level lowering below 13% [17%].

NO ATWS.

NO Station Blackout.

Initiating Cue:

Less than 200 GPM of feed water flow to the Steam Generators.

Both Steam Generators levels lowering.

RCS pressure is above the pressure of all Steam Generators.

Measurable

Prior to the need to establish bleed and feed, the crew manipulates controls to establish feed Performance water flow into at least one intact SG with one or more of the following:

Standard: o Auxiliary Feed Water Pumps o Main Feed Water Pumps o Condensate Pumps NOTES:

The crew establishing RCS bleed and feed instead of using a feed water source would most likely constitute a failure.

Steam Generator dry out indicated by BOTH of the following:

o Wide Range Level <13% [17%] AND o SG Pressure rapidly lowering or completely depressurized.

Performance

Increasing water level in at least one Steam Generator.

Feedback:

Feed water flow into at least one SG.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 5 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 CRITICAL TASK SHEET Number: PI-CT-19 Critical Task: Stop feed flow to the faulted Steam Generator within 45 minutes of this critical tasks plant conditions being met.

Safety Failure to stop feed flow to a Steam Generator that is faulted into Containment and can NOT be isolated Significance: will result in a challenge to the Containment Barrier.

Plant Conditions:

One faulted Steam Generator.

The fault is into Containment.

The fault can NOT be isolated.

A Red/Orange Path in Integrity CSF is likely and can NOT be prevented by crew actions.

Initiating Cue:

A single Steam Generator depressurizing in an uncontrolled manner or completely depressurized.

Main feed water or auxiliary feed water continues to be delivered to the faulted SG.

Measurable

Close/Secure the following valves/pumps aligned to the faulted Steam Generator (as necessary):

Performance o AFW Pump Discharge Valve(s)

Standard: o AFW Pump(s) o Main and Bypass Feed Water valve(s) o MFW Pump(s)

Performance

AFW flow to the faulted Steam Generator is secured.

Feedback:

SG Feed Water Flow to the faulted Steam Generator is secured.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 6 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS: EQUIPMENT OOS Exposure: MOC NONE Power: 1x10-8 AMPS Boron: (CB): 1575 PPM TAVG: 549°F Pressure: 2235 PSIG Xenon: Xe Free Rods: CBD @ 142 Generator: 0 MW SEQUENCE OF EVENTS:

Event 1: Secure 11 TDAFW Pump The crew will stop 11 TD AFW Pump per 1C28.1 and place in AUTO.

Event 2: Raise Reactor Power to the Point of Adding Heat

Reactor power is at 1 x 10-8 amps.

Rods will be stepped out to establish a positive startup rate.

Power will rise to between 0.5% and 2%.

Event 3: 12 Charging Pump Trip

PRZR level will go down.

The crew will respond per C47015-0104, 12 Charging Pump Trip.

The crew will start 13 Charging pump or increase 11 Charging pump speed.

Event 4: 11 TD AFW Pump Accumulator Low Air Pressure

Annunciator 47010-0105 will alarm.

The crew will close both steam supply valves to 11 TD AFW pump.

The crew will enter T.S. LCO 3.7.5 Condition B.

Event 5: 11 Containment Vacuum Breaker Fails Closed

CV-31621 11 Containment Vacuum Breaker will fail closed

47021-0101 11 CONTAIMNET VACUUM BREAKER CLOSED will alarm.

The crew will respond to the ARP and attempt to open CV-31621.

The SS will enter T.S. LCO 3.6.8 Condition A.

Event 6: 12 Steam Generator Fault to CTMT

12 SG level and pressure will lower, RCS pressure and PRZR level will lower.

SI will auto actuate.

The crew will isolate feedwater to 12 SG IAW 1E-2.

Event 7: 12 MD AFW pump fails to start automatically

The crew will manually start 12 MD AFW pump IAW 1E-0.

Event 8: SI to Feedwater/Condensate Relay Fails to Automatically Actuate

SI to Feedwater/Condensate relay fails to actuate on SI actuation.

The crew will manually align feedwater and condensate components IAW Att. L.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 7 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SIMULATOR PRE-BRIEF:

The Simulator Pre-Brief is conducted prior to the crew entering the simulator. Review the following with the off-going operator:

CREW COMPLETE TURNOVER:

Unit 1 LPEO / PEO Turnover Log

UNIT 1 LPEO / PEO TURNOVER LOG.

Walk-down the control boards and ask questions as

Verify crew performs walk down of control boards and appropriate reviews turnover checklists.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 8 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 1 Booth Operator / Communicator: 1C28.1, AUXILIARY FEEDWATER SYSTEM UNIT 1:

1. After the crew has assumed the duty, they will secure the BOP (N)

CLOSE MV-32238, 11 TD AFWP TO 11 STM GEN, 11 TD AFWP IAW the pre-job brief. using CS-46314.

2. When directed as an out-plant operator to verify 11 TD

CLOSE MV-32239, 11 TD AFWP TO 12 STM GEN, AFW Pump has stopped, CV-31153 has closed, and using CS-46315.

Auxiliary lube oil pump is running, then wait

Stop 11 TD AFW Pump using CS-46424.

approximately 2 minutes and report 11 TD AFW Pump is

Direct an out-plant operator to verify locally:

stopped, CV-31153 is closed, and Auxiliary lube oil pump o 11 TD AFW Pump has stopped.

is running. (1C28.1 steps 6.3.5 A, B, & C) o CV-31153, 11 TD AFW PMP RECIRC/L-O CLG

3. When directed as an out-plant operator to stop 11 TD CV, has CLOSED.

AFW Pump Aux Lube Oil Pump, then wait approximately o Auxiliary lube oil pump is running.

3 minutes and report Aux Lube Oil Pump has been

Direct an out-plant operator to locally stop 11 TD stopped. (1C28.1 step 6.3.6) AFW Pump Aux Lube Oil Pump when 11 TD AFW

4. If contacted as the duty chemist, acknowledge 11 TD Pump stops rotating.

AFW Pump has been stopped.

OPEN MV-32238, 11 TD AFWP TO 11 STM GEN, using CS-46314.

OPEN MV-32239, 11 TD AFWP to 12 STM GEN, using CS-46315.

Independently verify MV-32238 and MV-32239 are OPEN.

Verify SI Not Ready panel light 44102-A9, 11 AFW DISCH VLV CLOSED, is NOT LIT, indicating the discharge valves are OPEN.

Place CS-46438, 11 TD AFWP selector switch in AUTO.

Independently verify CS-46438 in AUTO.

Notify the Duty Chemist that 11 TD AFW Pump has been stopped.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 9 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 Booth Operator / Communicator: 1C1.2-M2, UNIT 1 STARTUP TO MODE 2:

1. After the crew has secured the 11 TD AFWP, they raise ATC (R)

Raise reactor power to the point of adding heat using reactor power to the POAH IAW the pre-job brief. manual rod control or boron concentration change.

SS (N)

When one or more intermediate range indicates greater than 1 x 10-9 amps, then verify ERCS is in Mode 2, STARTUP.

Using ERCS display XS02 and C41, verify the Plant Response: Subcritcality CSF Activation Status is INACTIVE.

1. Intermediate Range power will rise.

Maintain reactor power between 0.5 and 2.0%.

2. TAVG and PRZR level will rise.

3. Power Range power will come on scale.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 10 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3 Booth Operator / Communicator: C47015-0104, 12 CHARGING PUMP TRIP:

1. After the crew has stopped the 11 TD AFW Pump, and/or ATC (C)

If necessary, then start another charging pump.

at the discretion of the Lead Evaluator, then enter:

o Crew may start 13 Charging pump or may choose Trigger 3, 12 Charging Pump Trip to only increase the speed of 11 charging pump.

2. If contacted as Operations Management, acknowledge

Maintain pressurizer level and seal injection flow.

the report of the failure, and agree to make other

Determine reason for charging pump trip by checking notifications to the NRC, Duty Station Manager, etc. as the following:

asked. o Observe and log any VFD fault indicated on

3. If contacted as FIN team to write a CAP and WR 71116, 13 CHG PMP VFD CAB, and CS-acknowledge the request. 7111603, 13 CHG PMP SPEED CONT KEYPAD

4. If contacted as the outplant operator to investigate 12 Charging pump trip, wait 3 minutes and call back and

Reset a VFD Fault by performing the following:

state there are no VFD fault codes and no apparent o IF charging pump operation is NOT immediately cause. required, THEN obtain Engineering concurrence

5. If contacted as engineering for concurrence for resetting prior to resetting VFD fault a VFD fault, acknowledge the report and inform them you will investigate it and get back to them.

Plant Response:

1. 12 charging pump trips.

2. PRZR level lowers.

3. The following annunciators will alarm:

a. C47015-0104, 12 CHARGING PUMP TRIP.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 11 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 4 Booth Operator / Communicator: C47010-0105, 11 TD AFWP ACCUMULATOR LO AIR

1. After the crew has started 13 charging pump or increased BOP (C) PRESS:

11 charging pump speed, and/or at the discretion of the

Check for low air pressure on 18702, 11 TD AFW Lead Evaluator, then enter: PMP STM BLK VLV AIR ACCUM PI.

Trigger 4, 11 TD AFWP Accumulator Low Air Pressure

If a low air pressure condition exists, then notify the SS that 11 TD AFW pump is inoperable and enter

2. If contacted as Operations Management, acknowledge T.S. LCO 3.7.5 Condition B.

the report of the failure, and agree to make other

If 11 AFW pump is NOT running, then perform one of notifications to the NRC, Duty Station Manager, etc. as the following to prevent an undesired start of the pump asked. due to CV-31998 failing OPEN:

3. If contacted as the FIN Team Supervisor, inform the crew o CLOSE both steam supply valves to 11 TDAFW that you will write a CAP, Work Request, and assign an pump: MV-32016 & MV-32017.

I&C Supervisor to investigate. OR

4. If contacted as an outplant operator to investigate low air o Locally CLOSE CV-31059, 11 TD AFW PMP pressure condition, then inform the crew there is no TRIP THROTTLE CV.

SS (TS) apparent source. Gage 18702 is at 71 PSIG and lowering.

5. If contacted as an outplant operator to locally close CV- The SS will enter the following TS LCOs:

31059, then wait 3 minutes and inform the crew that the

3.7.5 Condition B:

valve is STUCK and will NOT close.

o Restore AFW train to OPERABLE status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND o 10 days from discovery of failure to meet the LCO Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 12 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 5 Booth Operator / Communicator: C47021-0101 11 CONTAINMENT VACUUM BREAKER

1. After the crew has closed TD AFWP steam supply valves CLOSED:

and addressed tech specs, and/or at the discretion of the

Check CV-31621, 11 CNTMT VSL VAC BKR ISOL Lead Evaluator, then enter: CV A, not fully OPEN Trigger 5, 11 Containment Vacuum Breaker Fails

Reopen valve unless it was closed due to a Closed Containment Isolation signal.

2. If contacted as the Operations Management,

IF no Containment isolation signal, THEN verify CV-acknowledge the report of the failure, and agree to make 31622, 12 CNTMT VSL VAC BKR ISOL CV B, OPEN other notifications to the NRC, Duty Station Manager, etc.

Refer to T.S. 3.6.8 as asked.

SS (TS) The SS will enter the following TS LCOs:

3. If contacted as FIN team to write a CAP and WR acknowledge the request.

3.6.8 Condition A:

o Restore vacuum breaker train to OPERABLE Plant Response: status within 7 days.

1. CV-31621 fails closed.

2. The following annunciator will be received:

a. 47021-0101, CONTAINMENT VACUUM BREAKER CLOSED Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 13 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTS Booth Operator/Communicator: 1E-0, REACTOR TRIP OR SAFETY INJECTION:

6, 7, & 8 ATC (M)

1. When the crew has addressed tech specs for the CTMT

Verify the reactor is tripped.

BOP (M) vacuum breaker, and/or at the discretion of the Lead SS (M)

Verify main turbine is tripped.

Evaluator, then enter:

Verify both Safeguards buses energized.

Trigger 6: 12 SG Fault to CTMT

Determine SI is required and/or actuated.

2. Upon hearing the announcement of Reactor Trip, or when called as the Turbine Building Operator to isolate

Perform Attachment L (see SEG pages 14 & 15)

ATC (C) the Unit 1 MSRs per Attachment J, then open and run SS (C)

Check AFW Status.

schedule file E-0_Att-J.sch located in CTs 10B o Manually start 12 MD AFW Pump X:\\Trex_PI\Lightning\Schedule\EOPs. Inform the & 19 o Stop feedwater flow to 12 SG crew when the MSRs are isolated.

3. Upon hearing the announcement of Safety Injection, or

Check RCS Temperatures trending to 547°F.

when called as the Turbine Building Operator to secure

Check PRZR PORVs and Spray valves closed.

the Turbine Building Roof Exhausters, wait 2 minutes,

If RCS pressure is less than 1600 PSIG, then STOP and report the Turbine Building Roof Exhausters are all both RCPs.

secured and NO Aux Building Vent Zones are open.

4. If contacted as an outplant operator to close TD-4-1,

Determine 12 SG is faulted & go to 1E-2.

then wait 2 minutes and inform the crew that TD-4-1 is closed. 1E-2, FAULTED STEAM GENERATOR ISOLATION:

5. If Control Room personnel ask if Unit 2 personnel are

Close 12 MSIV & verify 12 MSIV B/P is closed.

available to perform Attachment L, then inform the Control Room that Unit 2 personnel are NOT available

Identify 12 SG as the faulted generator.

for performing Attachment L. CT 19

Isolate the following from 12 SG:

6. If Control Room personnel ask if Unit 2 personnel are o main feedwater available to secure Diesel Generators and/or Safeguards Cooling Water Pumps, then inform the o AFW flow Control Room that Unit 2 personnel WILL secure the o Verify 12 SG PORV is closed.

Diesel Generators and/or Safeguards Cooling Water o Verify 12 SGB isolation valve is closed.

Pumps.

Check CST levels greater than 12,500 gallons.

7. If Control Room personnel ask for status of Battery Room Temperatures, then inform the Control Room that

Check secondary radiation normal.

Battery Room temperatures are 74°F.

Go to 1E-1.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 14 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTS 8. If Control Room personnel ask for status of Spent Fuel 1E-1, LOSS OF REACTOR OR SECONDARY 6, 7 & 8 Cooling, then inform the Control Room that Spent COOLANT:

cont. Fueling level and temperature are normal.

If RCS pressure is less than 1600 PSIG, then STOP

9. If Control Room personnel ask for status of Unit 2 both RCPs.

Cooling Water/Chilled Water lineup, then inform Crew Unit 2 Cooling Water/Chilled Water valves are in their

Determine 11 SG is NOT faulted.

Safeguards position.

Check 11 SG level >50% WR.

10. If contacted as Duty Chemist or Duty RP to check status

Check secondary radiation normal.

of secondary radiation levels and/or SG activity levels,

Verify both PORVs closed, power to both block then inform the control room that both SG cation column valves, and one block valve open.

frisks are reading background and secondary radiation levels are normal.

Reset SI.

11. If contacted as the Duty Chemist to initiate periodic

Reset CI.

samples of both Unit 1 SGs, then acknowledge the

Establish IA to CTMT.

request.

Check offsite power available to charging pumps.

Plant Response:

Determine SI pumps can or cannot be stopped.

1. 12 SG pressure lowers rapidly. (May transition to 1ES-0.2)

2. RCS & PRZR pressure lower.

Stop RHR pumps.

3. Containment Pressure rises.

1E-0 ATTACHMENT L: SI ALIGNMENT VERIFICATION:

CRITICAL TASKS BOP (C)

Verify Safeguards Component Alignment

PI-CT-10B: Establish feed water flow to the INTACT Steam SS (C)

Generator to prevent the INTACT Steam Generator from o See table on page 15 reaching DRYOUT conditions.

Close MV-32115, 122 SFP HX INLT HDR MV B

PI-CT-19: Stop feed flow to the faulted Steam Generator

Check Cooling Water Header Pressures within 45 minutes of this critical tasks plant conditions being met.

Verify plant announcements complete

Check If Main Steamlines Are required to be isolated

Verify SI & RHR Flow

Check RCP Cooling

Verify Generator Breakers - OPEN Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 15 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTS NOTE

Verify All Heater Drain Pumps - STOPPED 6, 7 & 8 The operator will have to perform the following to align

Open turbine drain valves cont. Safeguards Components for Safety Injection:

Verify Main Feedwater Alignment DESIRED CS # COMPONENT CONDITION

Verify All Condensate Pumps - STOPPED (Normally Aligned in Att. L) 46064 MV-32115, 122 SFP HX INLT HDR MV B CLOSED

Place Steam Dump in "STM PRESS" Mode 46018 11 CFCU SLOW

Verify Unit 1 Cooling Water/Chilled Water Alignment 46019 13 CFCU SLOW (Align due to Malfunctions)

Verify 11 Safeguards Screenhouse Ventilation lineup 46425 12 MD AFW PUMP ON

Verify Control Room Ventilation Alignment 46410 11 COND PUMP OFF 46418 11 FW PUMP OFF

Verify Unit 2 Cooling/Chilled Water Alignment 43062 CV-31127, A FW REG VLV DEMAND:

Verify 21 Safeguards Screenhouse Ventilation lineup ZERO DEMAND:

Verify 11 and 12 Battery Charger Operation is normal 43063 CV-31128, B FW REG VLV ZERO

Verify Battery Room temps less than 84°F DEMAND:

1HC480 CV-31369, A BYPASS FW ZERO

Check status of Spent Fuel Cooling 1HC481 CV-31370, B BYPASS FW DEMAND:

Check Status Of Notifications ZERO

Notify SS Of Any Discrepancies END Once the crew has isolated 12 SG and completed Att. L, and/or at the discretion of the Lead Evaluator, then place the simulator in FREEZE. Inform the crew training has the duty.

Booth Operator:

Collect SBT data per Attachment 1, if necessary.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 16 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 17 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Simulator Setup:

Beginning of Day:

1st / 2nd

___ / ___ 1. If it is the first scenario of the day, then perform a shutdown and restart of the floor PCs that are connected to the LAN.

___ / ___ 2. Log in on floor PCs with user ID & password: <pitrgsim>

___ / ___ 3. Verify on Adobe Acrobat Reader that the Restore Last View Setttings When Reopening Documents box is NOT checked. (Found under EDIT DOCUMENT)

___ / ___ 4. Update or Verify Control Room Placards:

a. NRC Code Placard:

i. NRC Current Authentication Code D3RF.

ii. Todays Date.

b. High Flux at Shutdown Alarm Setpoint placards: 5200 cps.

c. Feedwater regulating valve position placard set to current values.

d. Recommended SG Blowdown flow set to current values.

___ / ___ 5. Verify Current Plant Status Magnetic Placards are in Place:

a. Blowdown 46470 SGB To RIVER

b. H2 in VCT Space

c. 11 BA TANK Lined Up For Service

d. 11 BA PUMP Lined Up to 11 BA Tank

e. 12 BA PUMP Lined Up to 11 BA Tank

f. CC to SFP MV-32115 In Service

g. CC to SFP MV-32117 In Service

___ / ___ 6. Current Plant Pink Status Control Tags in place:

a. CS-46540, 22 CC WTR PUMP

b. CS-46572, 121 SFP HX INLT

___ / ___ 7. Current Plant Yellow Status Control Tags in place:

a. CS-46063, 11 CC HDR TO WST DISP HX MV-32102

___ / ___ 8. Verify that copy machine and printers are loaded with YELLOW BORDER paper.

___ / ___ 9. Pens/Notepads/Markers available on the simulator.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 18 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Simulator Setup:

NOTE: The time between simulator reset and placing simulator in RUN should be minimized to reduce the difference between the ERCS time and actual time.

1st / 2nd

___ / ___ 1. If this is the first scenario of the day, then perform Beginning of Day checklist on previous page.

___ / ___ 2. If an IC is already created for this scenario, then go to Step 4.

___ / ___ 3. If an IC is NOT created for this scenario, then create as follows:

a. Reset the simulator to IC-18.

b. Verify 1HC-484, MAIN STM HDR PRESS (STM DUMP), set point is set to 71.8% +/- 2%.

c. Place the simulator in RUN.

d. Verify RCS TAVG stabilized at 549°F.

e. Verify RCP Seal Injection at 8 GPM and charging flow balanced with letdown.

f. Adjust rods as necessary to establish reactor power at approx. 1 x 10-8 amps and stable.

g. Insert Remote SG100 to CW.

h. For 11 TD AFW Pump, perform the following:

i. Close MV-32238, 11 TD AFWP TO 11 STM GEN, using CS-46314.

ii. Close MV-32239, 11 TD AFWP TO 12 STM GEN, using CS-46315.

iii. Place CS-46438, 11 TD AFWP, to MANUAL.

iv. Start 11 TD AFWP using CS-46424.

v. Throttle MV-32238 and MV-32239 to establish 25 gpm to each SG.

i. Take the following to PULLOUT:

i. CS-46362, 4.16KV BUS 11 1M XFMR (BKR 11-4).

ii. CS-46363, 4.16KV BUS 12 1M XFMR (BKR 12-4).

iii. CS-46364, 4.16KV BUS 13 1M XFMR (BKR 13-9).

iv. CS-46365, 4.16KV BUS 14 1M XFMR (BKR 13-9).

j. OPEN SV-33341, AIR EJCTR LOOP SEAL DRN, using CS-46403.

k. Verify TPM is set to NIS.

l. If time permits, run simulator for approximately 30 minutes.

m. Place simulator in FREEZE.

n. If desired, save to available IC.

o. Go to step 4.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 19 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Simulator Setup cont.:

___ / ___ 4. Reset the Simulator to IC-251 and place in RUN.

a. Verify TAVG is stable @ ~549°F. If necessary, adjust Steam Dump SETPOINT DIAL to maintain temperature.

___ / ___ 5. If available, run schedule file PI-ILT-NRC-2001S.sch as follows:

a. Locate schedule file.

b. Open schedule file by double clicking it.

c. Run the schedule file by pressing the Stopped button on the toolbar.

d. Verify the schedule file is running.

___ / ___ 6. If schedule file is NOT available, reset Simulator to IC-251 or IC created in step 3, place in RUN, and insert malfunctions, remotes, and overrides, as specified by the Simulator Input Summary.

___ / ___ 7. Mark up 1C1.2-M2, Unit 1 Startup to Mode 2, sections 5.1-5.3. N/A or leave blank any appropriate steps.

___ / ___ 8. If desired, start Scenario Based Testing Data Collection Program per Att 1.

___ / ___ 9. Complete the "Simulator Setup Checklist on next page.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 20 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 SIMULATOR SETUP CHECKLIST Pre-Scenario Checklist:

1st / 2nd

_ _/ _ Simulator Status:

___1. "Training Load" ___4. Step counters: NOT USED

___2. Alarm sound: ON ___5. Simulator running in IC-18 or IC-251.

___3. Speed: REAL ___6. Steps 1 - 8 on previous page complete.

_ _/ _ Delete memory on Yokogawa Model DX1000 recorders by cycling Recorder Power.

_ _/ _ Verify Schedule File/Summary matches Simulator Input Summary page in the SEG.

_ _/ _ Verify that control rod step counters on C panel and ERCS RBU CBD @ 142.

_ _/ _ Boric Acid/RMU integrators set to: BA: 0, RMU: 20, and RESET.

_ _/ _ MOC I sheet displayed on C panel.

_ _/ _ MOC Reactivity Briefing sheet available at Reactor Operator Desk.

_ _/ _ Verify Boric Acid and Reactor Makeup Controllers are set properly:

___ 1. 1HC-110: 34.6%

___ 2. 1HC-111: 44.7%

_ _/ _ Update or Verify SEG specific Control Board Placards:

___ 1. CVCS panel placard:

a. RCS boron - 1575 ppm.

b. RCS H2 - 45 cc/kg.

c. Turbine Reference Value and Mode - matched with DEHC.

___ 2. Shift Reactivity Guidance placard:

a. BA: 0 gallons

b. RMU: 0 gallons

c. Dilutions @ N/A

___ 3. EAL Classification Placard CLEANED and placed on side of SS desk.

___ 4. LCO Timer CLEANED.

_ _/ _ SEG specific Magnetic Placards in place:

_ _/ _ ___ 1. NONE

_ _/ _ SEG specific or Protected Equipment Pink Status Control Tags in place:

_ _/ _ ___1. NONE

_ _/ _ SEG specific or Out of Service Yellow Caution Tags are in place:

___ 1. NONE Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 21 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Pre-Scenario Checklist continued:

1st / 2nd

_ _/ _ ERCS driven recorders are on-scale (RCS temperature scaled 545º F to 555º F).

_ _/ _ ERCS alarm screen operating and alarms reset.

_ _/ _

All ERCS terminals operating and set as follows:

CONF VARS R02 Alarm Summary Page CONE1 Group OP31_U1 R03 AFD CONC SAS (XS11) R04 TPM CONG1 Group QP CCDATA R05 QP LOADFOLL ERCS-R01 Group RADMON_U1 R06 Alarm Summary Page

_ _/ _ ERCS single point displays:

CONB 1T0499A 1U1613A CONE2 1Q0340A 1V4501A

_ _/ _ ERCS TPM set (NIS - Auto Scaling - Venturi).

_ _/ _ Set Turbine Control HMI Displays as follows:

___ 1. U1 E-H Turb Cont STA 2 (48087) to Control Valve Overview

___ 2. U1 Turb Aux Cont (48088) to Turb Overview

___ 3. U1 E-H Turb Cont STA 1 (48086) to On Line Control

___ 4. DEHC alarms cleared.

_ _/ _ YELLOW turnover sheets 1-9 available.

_ _/ _ All Fire alarms CLEAR.

_ _/ _ Electronic PINGP 577 forms and TABS closed on both LAN connected PCs.

_ _/ _ Board-mounted EAL Tables are cleaned.

_ _/ _ Headsets turned on as necessary.

_ _/ _ Procedure checklist completed. See following page.

_ _/ _ Peer Check performed for simulator setup.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 22 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 PROCEDURE CHECKLIST:

NOTE: The following procedures will be used during this session. Verify the procedures are free of place keeping marks before starting the session and after the session are complete.

Before After 1st / 2nd 1st / 2nd

/ / 1C1.2-M2, UNIT 1 STARTUP TO MODE 2

/ / 1C28.1, AUXILIARY FEEDWATER SYSTEM UNIT 1

/ /

/ / C47010-0105, 11 TD AFWP ACCUMULATOR LO AIR PRESS

/ / C47021-0101 11 CONTAINMENT VACUUM BREAKER CLOSED

/ / C47015-0104, 12 CHARGING PUMP TRIP

/ /

/ / 1E-0, REACTOR TRIP OR SAFETY INJECTION

/ / 1E-0, ATT. L, SI ALIGNMENT VERIFICATION

/ / 1E-1, LOSS OF REACTOR OR SECONDARY COOLANT

/ / 1E-2, FAULTED STEAM GENERATOR ISOLATION

/ / 1E-CAS, UNIT 1 CONTINUOUS ACTION & INFO PAGE

SUMMARY

/ /

/ / EAL BOARD

/ /

/ / LAMINATE COPY OF 1C5, SECTION 5.5

/ / LAMINATE COPY OF 1C12.5, SECTIONS 5.8 & 5.9

/ / LAMINATE COPY OF 1C12.5, SECTION 5.10

/ / LAMINATE COPY OF 1C1.4 AOP1, RAPID LOAD REDUCTION UNIT 1

/ /

/ / REACTIVITY BRIEFING SHEET - MOC

/ /

/ / SWI O-28, NOTIFICATION OF OPS MNGR & NRC RESIDENT INSPECTOR

/ /

/ / T.S. LCO 3.3.1

/ / T.S. LCO BASES 3.3.1

/ / T.S. LCO 3.3.2

/ / T.S. LCO BASES 3.3.2

/ /

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 23 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Post-Scenario Checklist 1st / 2nd

_ _/ _ Computer generated PINGP 577 cleared and tab closed.

_ _/ _ Verify no electronic procedures are open on either Sim Floor computer.

_ _/ _ Verify recent history on IE and Adobe are clear for BOTH Sim Floor computers.

_ _/ _ Procedure checklist completed. See previous page.

_ _/ _ Remove Pink Status Control Tags from the following equipment:

___1. NONE

_ _/ _ Remove Magnetic placards from Control Boards:

___ 1. EAL Classification Placard from Control Board.

___ 2. RED/WHITE Critical Parameter Cards

_ _/ _ Remove Yellow Caution Tags from the following equipment:

___ 1. NONE

_ _/ _ Board-mounted EAL Table is cleaned.

_ _/ _ All books, note pads, and calculators put away.

End Of Day Checklist 1st / 2nd

_ _/ _ Signs/placards removed and put away unless normal simulator configuration.

_ _/ _ If desired, floor PCs logged off if simulator will not be used again that day.

_ _/ _ Instructor station returned to normal with all books, paper, and pens, etc. put away.

_ _/ _ Headsets turned off and put away if simulator will not be used again that day.

_ _/ _ Simulator reset to IC-10 unless another IC will be used for further training.

_ _/ _ Simulator placed in DORT if simulator will not be used again that day.

_ _/ _ Verify the following placards are erased:

CVCS panel

Shift Reactivity Guidance

LCO Timer

NRC Authentication Code Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 24 of 28 RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: 8/17/2020 DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS

NONE PROTECTED EQUIPMENT SFP COOLING RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Exposure: MOC Pressure: 2235 PSIG Unit 2 is at 100% power.

Power: 1x10-8 Xenon: Free Boron (CB): 1575 PPM Rods: CBD @ 142 TAVG: 549°F Generator: 0 MW MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE NONE OPERATIONAL PLANS FOR COMING SHIFT Stop 11 TD AFW pump and place in AUTO per 1C28.1, 6.3.

Raise reactor power to the POAH per 1C1.2-M2, 5.4.

NEW PROCEDURES / INSTRUCTIONS 11 TD AFW Pump is running for transition to MFW.

of 9 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 25 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

1. The scenario contains objectives for the desired tasks and relevant human Yes No performance tools. X

2. The scenario identifies key parameter response, expected alarms, and Yes No automatic actions associated with the induced perturbations. X

3. The scenario content adequately addresses the desired tasks, through Yes No simulator performance, instructor-led training freezes, or both. X

4. Plant PRA initiating events, important equipment, and important tasks are Yes No identified. X

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Yes No Assessment. Justification: PRA software not installed on Sim computers. X

6. The scenario contains procedurally driven success paths. Procedural Yes No discrepancies are identified and corrected before training is given. X

7. The scenario guide includes responses for all anticipated communications to Yes No simulated personnel outside the Control Room, based on procedural guidance X and standard operating practices. Include estimated completion times and/or notes for use of time compression.

8. The scenario includes related industry experience. SOER, SER and similar Yes No OE recommendations are clearly identified and fully addressed.* X

9. The scenario guide incorporates verification of Operator Fundamental Yes No application.* X

10. Training elements and specific human performance elements are addressed Yes No in the scenario critique guide to be used by the critique facilitator. The critique X guide includes standards for expected performance.*

11. For evaluations, it has been verified that without operator action the critical Yes No tasks will be failed. X Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

For evaluations these items may be marked NO without justification.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 26 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial conditions agreed with the reference plant with Yes No respect to reactor status, plant configuration, and system operation. X

2. The simulator operated in real time during conduct of validation. Yes No X

3. The simulator demonstrated expected plant response to operator input Yes No and to normal, transient, and accident conditions. X

4. The simulator permitted use of the reference plants procedures. The Yes No scenario was completed without procedural exceptions, simulator X performance exceptions, or deviation from the scenario sequence.

5. The simulator did not fail to cause or unexpectedly cause any first Yes No principle alarm or primary automatic action. X

6. Observable changes in parameters relevant to the scenario Yes No corresponded in trend and direction to reference plants expected X response.

7. All malfunctions and other instructor interface items were functional and Yes No demonstrated the expected reference plants response to the initiating X cause.

8. All malfunctions and other instructor interface items were initiated in the Yes No same sequence described within the simulator scenario. X

9. The scenario satisfies the learning or examination objectives without Yes No any significant simulator performance issues, or deviations from the X approved scenario sequence.

10. Simulator fidelity has been demonstrated to be adequate for this Yes No scenario. X Discrepancies noted (Check none or list items found) None SMAR = Simulator Action Request SMAR: SMAR: SMAR: SMAR:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 27 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Comments:

Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Validation Personnel Name Job Title / Qualification Validation Position VELASCO SRO SS HELLAND RO BOP LODERMEIER RO ATC Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Rev. 0 (12/14/2018) Page 28 of 28 PI-ILT-NRC-2001S, 2020 ILT NRC SIMULATOR EVALUATION #1, REV. 0 ATTACHMENT 1 SBT EXAM DATA COLLECTION

BEFORE SCENARIO o START menu o SBT Report o File o OPEN o Select file type .tis (FILE LOCATION: sim data (X:) / TRex_PI / LIGHTNING / SBT o Select SBT.tis o OPEN or double click o Check TAM log & verify no cycling switches o Run scenario

AFTER SCENARIO o FREEZE on Simulator o Click GREEN arrow to generate report o Enter the following:

(NAME is not required)

Test Title (2001S ILT NRC SBT Group x)

Report Name (same as test title) o Click the button to right of Report Name field.

o Select location where file is to be saved (on Locker G3 flash drive) o Enter file name (same as report name) & SAVE o Click GENERATE, verify file location, and close html file o START menu o COMPARE IT o Click + ADD o Select .csv file from previously saved location o OPEN or double click o Click GREEN COMPARE button o Wait for spreadsheet to populate and then save in desired location o Verify all 3 files are saved in proper location o Close spreadsheet, COMPARE IT, and SBT Report Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 1 of 27 SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # PI-ILT-NRC-2002S SEG TITLE: 2020 ILT NRC SIMULATOR EVALUATION #2 REV. # 0 PROGRAM: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT COURSE: INITIAL LICENSE OPERATOR TRAINING #: FL-ILT TOTAL TIME: 2.0 HOURS Additional site-specific signatures may be added as desired.

Developed by: Fredrick Collins Instructor Date Reviewed by: Justin Hasner Instructor Date (Simulator Scenario Development Checklist.)

Validated by: Justin Hasner Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 2 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Guide Requirements Evaluation Evaluate the crews ability to:

Objectives:

1. Swap EH Oil Pumps per 1C23.

Evaluate the crews ability to diagnose and respond to:

2. Pressurizer Pressure Instrument failing low per 1C51.2.

3. Emergency Diesel Generator Local Alarm per C47024.

4. Turbine EH valve malfunction per 1C23 AOP2.

5. Rapid Load Reduction per 1C1.4 AOP1.

6. Loss of All Onsite and Offsite Power per 1E-0 and 1ECA-0.0.

7. Main Turbine fails to automatically trip per 1E-0.

8. Failure of D2 EDG to automatically start per 1ECA-0.0.

9. Failure of 12 MD AFW Pump to auto start per 1ECA-0.0.

Training 1. Full Scope Simulator Resources: 2. NRC Evaluation Team

3. Booth Operator (Backup Communicator)

4. Primary Communicator Related PRA Initiating Event with Core Damage Frequency:

Information: Loss of Offsite Power (20.3%)

Important Components:

12 MD AFW PMP D2 DSL GEN Important Operator Actions with Task Number:

CRO 000 055 05 01 000 - Loss of Offsite and Onsite Power CRO 062 ATI 00 00 017 - Energize a Dead 4.16KV Bus Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 3 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 1P-431, PRZR Pressure Blue Channel Fails Low.

2. Turbine EH Valves Fail Closed.

After EOP Entry:

1. Main turbine auto trip failure.

2. D2 Emergency Diesel Generator fails to start automatically.

3. 12 MD AFW pump fails to start.

Abnormal Events:

1. Instrument Failure Guide.

2. Rapid Load Reduction Major Transients:

1. Loss of All Onsite and Offsite AC Power Critical Tasks:

1. PI-CT-6: Energize at least one AC emergency bus when safeguards equipment is required to perform its safety function or prior to ORANGE or RED path on Core Cooling CSF.

2. PI-CT-11: During a Station Blackout, establish Auxiliary Feedwater flow to the Steam generators to prevent both Steam Generators from reaching DRYOUT conditions.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 4 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 CRITICAL TASK SHEET Number: PI-CT-6 Critical Task: Energize at least one AC emergency bus when safeguards equipment is required to perform its safety function or prior to ORANGE or RED path on Core Cooling CSF.

Safety Failure to energize an AC emergency bus when an AC power source is available Significance: unnecessarily makes safeguards equipment unavailable when needed.

Plant Conditions:

Loss of Bus 15 AND Bus 16.

At least one source is available to supply power to Bus 15 or Bus 16.

Cues:

Bus 15 and bus 16 is de-energized.

All source breakers to buses 15 and 16 are open or tripped.

Performance

Manipulation of controls to establish one safeguards bus powered from an Indicator: available source.

Feedback:

Bus 15 or 16 is energized.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 5 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 CRITICAL TASK SHEET Number: PI-CT-11 Critical Task: During a Station Blackout, establish Auxiliary Feed Water flow to the Steam Generators to prevent both Steam Generators from reaching DRYOUT conditions.

Safety With insufficient feed water flow, the Steam Generators dry out, causing an RCS Significance: pressure increase that opens the pressurizer PORVs. The open PORVs create a small break LOCA that challenges the Core Cooling CSF. Failure to maintain an adequate heat sink will result in degradation of the Fuel Clad Barrier and RCS Barrier.

Plant Conditions:

Loss of Offsite Power.

Loss of Bus 15 AND Bus 16.

11 TD AFW Pump fails to automatically start.

11 TD AFW Pump is capable of being started from the Control Room.

Cues:

11 TD AFW Pump not running.

One or more Steam Generator NR Levels drop below 13%.

Indications of a Station Blackout.

Performance

11 TD AFW Pump selector switch placed in MANUAL.

Indicator:

11 TD AFW Pump hand switch momentarily placed in START.

NOTES:

Steam Generator dry out indicated by BOTH of the following:

o Wide Range Level <13% [17%] AND o SG Pressure rapidly lowering or completely depressurized.

Feedback:

Increasing water level in at least one Steam Generator.

Feed water flow into at least one SG.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 6 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS: EQUIPMENT OOS Exposure: EOC 11 TD AFWP Power: 100%

Boron: (CB): 102 PPM TAVG: 560°F Pressure: 2235 PSIG Xenon: Equilibrium Rods: CBD @ 218 Generator: 582 MW SEQUENCE OF EVENTS:

Event 1: Swap Running EH Oil Pumps

11 EH Oil pump is running.

The crew will start 12 EH Oil pump and stop 11 EH Oil pump per 1C23.

Event 2: 1P-431, Blue Channel Pressurizer Pressure, fails LOW.

PRZR Level Blue Channel 1P-431 will fail low.

The crew will place PRZR level control in RED-BLUE (1-3).

The Shift Supervisor will enter TS LCO 3.3.1 Conditions A & K.

Event 3: C47024-1203, D1 Local Alarm

The D1 Local Alarm will come in due to low starting air pressure.

The SS will enter TS LCO 3.8.1 Condition B.

Events 4 & 5: Turbine EH Valve Malfunction / Rapid Load Reduction

Diagonally opposite turbine control IVs will fail closed.

The crew will determine a rapid load reduction is required per 1C23 AOP2.

The crew will perform a Rapid Load Reduction per 1C1.4 AOP1.

Event 6: Loss of All AC Power

The reactor will trip upon loss of all AC due to loss of flow.

The crew will enter 1E-0 then transition to 1ECA-0.0.

The crew will have to manually start D2 and place D2 EDG on Bus 16 to restore power to a U1 safeguards bus.

Event 7: Main turbine fails to automatically trip

The crew will manually start D2 per 1ECA-0.0.

Event 8: D2 fails to start automatically

The crew will manually start D2 per 1ECA-0.0.

Event 9: 12 MD AFW pump fails to start automatically

The crew will manually start 11 TD AFW pump per 1ECA-0.0.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 7 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SIMULATOR PRE-BRIEF:

The Simulator Pre-Brief is conducted prior to the crew entering the simulator. Review the following with the off-going operator:

CREW COMPLETE TURNOVER:

Unit 1 LPEO / PEO Turnover Log

UNIT 1 LPEO / PEO TURNOVER LOG.

Walk-down the control boards and ask questions as

Verify crew performs walk down of control boards and the appropriate.

reviews turnover checklists.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 8 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 1 Booth Operator / Communicator: 1C23, UNIT 1 TURBINE CONTROL SYSTEM:

1. After the crew has assumed the duty, they will swap

Station an operator at the EH Oil Skid.

running EH Oil pumps per 1C23 and pre-job brief. BOP (N)

If swapping from 11 EH Oil pump to 12 EH Oil pump,

2. If directed as the Outplant Operator to verify proper EH then perform the following:

Oil Pump operation, then wait 2 minutes and report back o Start 12 EH Oil Pump by placing CS-46385, 12 that the pump is operating properly. EH OIL PUMP, to START.

o Locally verify proper pump operation.

Stop 11 EH Oil Pump by placing CS-46384, 11 EH OIL PUMP, in STOP.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 9 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 Booth Operator / Communicator: C47012-0108, PRZR LO PRESS SI CHANNEL ALERT

1. After the crew has swapped EH oil pumps, and/or at the ATC (I)

Check pressurizer pressure.

discretion of the Lead Evaluator, enter:

Verify all heaters ON.

Trigger 2, PRZR Press Cont. (Blue) Channel fails LOW.

Verify sprays CLOSED.

2. If contacted as I&C to trip bistables, inform the crew two

If necessary, then control pressure in manual.

I&C Technicians will be available in 45 minutes.

Refer to 1C51.3.

3. If contacted as the Operations Management, acknowledge the report of the failure, and agree to make 1C51.3, PRESSURIZER PRESSURE 1P-431 - LOW other SWI O-28 notifications to the NRC, Duty Station

Place PRZR Pressure controller in MANUAL and Manager, etc. STABILIZE pressure.

4. If contacted as the FIN Team Supervisor, inform the crew

Select position 2-1 (WHITE-RED) on PRZR Pressure that you will write a work order and assign an I&C Selector switch.

Supervisor to investigate.

When pressure is returned to normal with no deviation from setpoint, then return pressure control to auto.

Plant Response:

Ensure PRZR Pressure Recorder not selected to Blue

1. PRZR backup heaters energize. channel.

2. The following annunciators will alarm:

a. 47012-0108, PRZR LO PRESS SI CHANNEL ALERT

b. 47012-0408, PRZR HI/LO PRESS CHANNEL ALERT

c. 47012-0504, REACTOR COOLANT SYSTEM OVERTEMP T CHANNEL ALERT

d. 47012-0608, PRZR CONTROL HI PRESS OR BACKUP HTRS ON

e. 47013-0205, OTT ROD STOP TURBINE RUNBACK CHANNEL ALERT Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 10 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 The SS will enter the following TS LCOs:

cont.

SS (TS)

3.3.1 Condition A:

o Enter conditions referenced in Table 3.3.1-1 IMMEDIATELY.

3.3.1 Condition E:

o Place channel in trip in 6 HOURS OR o Be in MODE 3 in 12 HOURS

3.3.1 Condition K:

o Place channel in trip in 6 HOURS.

OR o Reduce thermal power to <P-7 & P-8 in 12 HOURS.

3.3.2 Condition A:

o Enter conditions referenced in Table 3.3.2-1 IMMEDIATELY.

3.3.2 Condition D:

o Place channel in trip in 6 HOURS OR o Be in MODE 3 in 12 HOURS AND o Be in MODE 4 in 18 HOURS Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 11 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3 Booth Operator / Communicator: C47024-1203, D1 EMERGENCY GENERATOR LOCAL

1. When the crew has returned pressure control to auto and ALARM:

addressed Tech Specs and/or at the discretion of the

Dispatch an operator to D1 Diesel Generator Control Lead Evaluator, then enter: Room to respond to the alarm per C55300.

Trigger 3, D1 Local Alarm.

Refer to T.S. 3.8.1, as necessary.

2. If contacted as an outplant operator to investigate D1 local alarm, wait 2 minutes, then inform the crew that the C55300-0101, STARTING AIR PRESSURE LOW:

common line between main and reserve air receiver is

Investigate cause of low air pressure.

sheered, the line is unisolable, that starting air system pressure is at 0 PSIG, and you are responding per C55300-

Isolate leak or start air compressor.

0101.

If unable to restore starting air system pressure, then

3. When asked whether the rupture can be isolated, inform consider using crosstie.

the crew the rupture CANNOT be isolated and the air

If at least one air receiver cannot be maintained in-compressor cannot keep up. service and at >175 psig, then the diesel generator

4. If contacted as the outplant operator to attempt a crosstie does not meet its design requirements and operability between D1 & D2, wait 2 minutes, then inform the crew must be determined. Refer to T.S. 3.8.1.

that a crosstie valve is stuck in the closed position and crosstie is not available. 1C20.7, Precaution 3.17 contains guidance on air receiver

5. If asked as a Unit 2 operator to perform SP 1118, then pressure (>175 PSIG) and DG operability.

inform the crew Unit 2 will perform SP 1118 for Unit 1.

6. If asked as an outplant operator to determine if D2 has a common cause failure, then wait 2 minutes and inform the crew that D2 starting air system pressure is at 195 PSIG and stable.

7. If contacted as the Operations Management, acknowledge the report of the failure, and agree to make other SWI O-28 notifications to the NRC, Duty Station Manager, etc.

Plant Response:

1. Annunciator 47024-1203 will alarm.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 12 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3 The SS will enter the following TS LCOs:

cont.

SS (TS)

3.8.1 Condition B:

o Perform SP 1118 in 1 HOUR AND o Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable within 4 HOURS of discovery.

AND o Determine OPERABLE DG is not inoperable due to a common cause failure in 24 HOURS.

AND o Restore DG to OPERABLE status in 14 DAYS.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 13 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTS Booth Operator / Communicator: 1C23 AOP2, MALFUNCTION OF TURBINE EH 4&5 1. After the crew has addressed tech specs and/or at the CONTROL SYSTEM:

BOP (C) discretion of the Lead Evaluator enter:

Determine that 2 IVs from diagonally opposite MSRs Trigger 4, Turbine Control IV Malfunction have CLOSED.

2. If contacted as the out-plant operator to investigate, wait

Reduce turbine load to 50% per 1C1.4 AOP1.

2 minutes and report there are no indication of an EH Oil System problem. 1C1.4 AOP1, RAPID POWER REDUCTION - UNIT 1:

3. If contacted as the Operations Management, ATC (R)

Determine predicted boron addition and final control acknowledge the report of the failure, and agree to make SS (N) rod position from contingency reactivity plan for the other notifications to the NRC, Duty Station Manager, target power level.

etc. as asked.

4. If contacted as the FIN Team Supervisor or Turbine

Borate RCS to maintain control rods above insertion Engineer, inform the crew that you will write a work order limit and control delta I within limits.

and investigate.

Place PRZR heaters to ON.

Reduce turbine load to desired value.

Plant Response:

1. Turbine control IVs CV-31167 & 31173 fail closed.

2. TAVG will rise.

3. Turbine load will lower.

4. The following annunciators will be received:

a. 47008-0409, TURB CONTROL SYSTEM TROUBLE NOTE:

It is not necessary to complete the full down power prior to moving on to the next event.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 14 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTS Booth Operator / Communicator: ATC (M) 1E-0, REACTOR TRIP OR SAFETY INJECTION 6, 7, & 8

1. When the crew has initiated a rapid load reduction, BOP

Verify reactor is tripped.

(C & M)

Manually trip the main turbine.

and/or at the discretion of the Lead Evaluator, then enter: SS (M)

Trigger 6, Loss of All AC.

Determine both Safeguards buses NOT energized.

Transition to 1ECA-0.0.

2. Wait 1 minute & announce over PA, Attention all plant personnel, Unit 2 Reactor Trip. Unit 2 Reactor Trip.

1ECA-0.0, LOSS OF ALL SAFEGUARDS AC POWER

3. If contacted as an out-plant operator to report seal injection flow, then wait 3 minutes and report to the

Check PRZR PORVs CLOSED.

control room seal injection flow as indicated on

Check Letdown isolation valves CV-31255 & CV-THUNDERVIEW-SIMVC02. 31226 CLOSED.

4. If contacted as an out-plant operator to investigate and/or

Check Excess Letdown isolation valve CV-31330 Acknowledge the D2 Local Alarm, then report that it is CLOSED.

due to C55800-0105, Stand-By Lube Oil System Trouble

Determine AFW flow is NOT greater than 200 gpm.

alarm and enter REMOTE: DG107 to SILENCE.

Announce Unit 1 reactor trip.

5. When the crew places synchroscope in D2, verify AUTO

Determine CL header pressure greater than 25 PSIG.

Trigger 16 is entered.

Determine Bus 16 is available.

6. If crew asks if a Unit 2 operator is available to work on BOP (C)

Start D2 diesel generator.

restoring Bus 15, then inform the crew that Unit 2 WILL SS (C)

Place BKR 16-9 MAN/AUTO switch to MANUAL work on restoring Bus 15. CT 6

Place synchroscope select switch to D2

7. If contacted as an out-plant operator to establish

Close BKR 16-9.

communications with the CR to throttle AFW flow, then

Verify Bus 16 energized.

wait 2 minutes and report via handheld radio that you are

Start one charging pump.

in the AFW Pump room standing by to throttle AFW flow.

Return to 1E-0, step 3.

CRITICAL TASKS 1E-0, REACTOR TRIP OR SAFETY INJECTION

PI-CT-6: Energize at least one AC emergency bus when

Determine Bus 16 energized.

safeguards equipment is required to perform its safety function or

Determine SI is NOT actuated nor required.

prior to ORANGE or RED path on Core Cooling CSF.

Transition to 1ES-0.1.

PI-CT-11: During a Station Blackout, establish Auxiliary Feedwater flow to the Steam generators to prevent both Steam Generators from reaching DRYOUT conditions.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 15 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENTS 8. Throttle AFW flow as necessary using the following 1ES-0.1, REACTOR TRIP RECOVERY 6, 7, & 8 remotes:

Transfer steam dump to STM PRESS mode.

cont. a. FW136 - 12 AFW Pump to 11 SG (MV-32381)

Check RCS cold leg temps at 547°F.

b. FW137 - 12 AFW Pump to 12 SG (MV-32382)

Check CL header pressure greater than 75 psig.

ATC (C)

Notify TBO to perform Att. J.

NOTE: SS (C)

Determine AFW flow to SGs less than 200 gpm.

It takes approximately 3 minutes for AFW MVs to CT 11 o Start 12 MD AFW pump.

fully close after the remote has been entered.

Determine all control rods NOT fully inserted.

Ensure MV shows closed on Thunderview prior to telling crew the valve is closed.

1FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT Plant Response: SINK:

1. Reactor trip.

Determine secondary heat sink is required.

2. Bus 15 locks out and Bus 16 de-energizes.

Determine bleed & feed is NOT required.

3. D1 locks out & D2 fails to start.

Restore AFW to at least one SG.

4. Multiple annunciators associated with loss of power. o Start 12 MD AFW pump.

NOTE: Depending on crew timing, a RED PATH in Heat Sink CSF may come in due to turbine auto trip failure.

This is NOT a failure. The crew will then restore AFW in 1FR-H.1 and return to procedure and step in effect.

END Once the crew has restored power to Bus 16 and started 12 MD AFW pump, and/or at the discretion of the Lead Evaluator, then place the simulator in FREEZE. Inform the crew that training has the duty.

Booth Operator:

Collect SBT data per Attachment 1.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 16 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SIMULATOR INPUT

SUMMARY

SIMULATOR EVENT

SUMMARY

Event ID Description Code 16 RESTORE BKR 16-9 HWZDGD6906(2)==1 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 17 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Simulator Setup:

Beginning of Day:

___ 1. If it is the first scenario of the day, then perform a shutdown and restart of the floor PCs that are connected to the LAN.

___ 2. Log in on floor PCs with user ID & password: <pitrgsim>

___ 3. Update or Verify Control Room Placards:

a. NRC Code Placard:

i. NRC Current Authentication Code D3RF.

ii. Todays Date.

b. High Flux at Shutdown Alarm Setpoint placards: 5000 cps.

c. Feedwater regulating valve position placard set to current values.

d. Recommended SG Blowdown flow set to current values.

___ 4. Verify Current Plant Status Magnetic Placards are in Place:

a. Blowdown 46470 SGB to CDSR

b. H2 in VCT Space

c. 11 BA TANK Lined Up for Service

d. 11 BA PUMP Lined Up to 11 BA Tank

e. 12 BA PUMP Lined Up to 11 BA Tank

f. CC to SFP MV-32115 In Service

g. CC to SFP MV-32117 In Service

___ 5. Current Plant Pink Status Control Tags in place:

a. CS-46540, 22 CC WTR PUMP

b. CS-46572, 121 SFP HX INLT

___ 6. Current Plant Yellow Caution Tags in place:

a. NONE

___ 7. Verify that copy machine and printers are loaded with YELLOW BORDER paper.

___ 8. Pens/Notepads/Markers available on the simulator.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 18 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Simulator Setup:

NOTE: The time between simulator reset and placing simulator in RUN should be minimized to reduce the difference between the ERCS time and actual time.

___ 1. If this is the first scenario of the day, then perform Beginning of Day checklist on previous page.

___ 2. Reset the Simulator to IC-252 and go to step 4.

___ 3. If IC-252 is not available, then perform the following:

a. Reset the Simulator to IC-11 and place in RUN.

b. Place CS-46424, 11 TD AFW Pump in PULLOUT.

c. Place CS-46438, 11 TD AFWP in MANUAL.

d. Close 11 MAIN STM TO 11 TD AFWP MV-32016 using CS-46127.

e. Close 12 MAIN STM TO 11 TD AFWP MV-32017 using CS-46128.

f. Close MV-32238, 11 TD AFWP TO 11 STM GEN, using CS-46314.

g. Close MV-32239, 11 TD AFWP TO 12 STM GEN, using CS-46315.

___ 4. Place the simulator in RUN.

___ 5. If available, run schedule file PI-ILT-NRC-2002S.sch as follows:

a. Locate schedule file.

b. Open schedule file by double clicking it.

c. Run the schedule file by pressing the Stopped button on the toolbar.

d. Verify the schedule file is running.

___ 6. If schedule file is NOT available, then insert malfunctions, remotes, and overrides, as specified by the Simulator Input Summary.

___ 7. If available, run event file PI-ILT-NRC-2002S.evt as follows:

a. Locate event file.

b. Open event file by double clicking file.

___ 8. If event file is NOT available, then enter event codes as specified by Simulator Event Summary.

___ 9. If desired, start Scenario Based Testing Data Collection Program per Attachment 1.

___ 10. Complete the "Simulator Setup Checklist on next page Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 19 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SIMULATOR SETUP CHECKLIST Pre-Scenario Checklist:

_____ Simulator Status:

___1. "Training Load" ___4. Step counters: NOT USED

___2. Alarm sound ON ___5. Simulator running in IC-252 or IC-11.

___3. Speed: REAL ___6. Steps 1 - 9 on previous page complete.

_____ Delete memory on Yokogawa Model DX1000 recorders by cycling Recorder Power.

_____ Verify Schedule File/Summary matches Simulator Input Summary page in the SEG.

_____ Verify that control rod step counters on C panel and ERCS RBU CBD @ 218.

_____ Boric Acid/RMU integrators set to: BA: 0, RMU: 20, and reset.

_____ EOC I sheet displayed on C panel.

_____ EOC Reactivity Briefing sheet available at Reactor Operator Desk.

_____ Verify Boric Acid and Reactor Makeup Controllers are set properly:

___ 1. 1HC-110: 2.1%

___ 2. 1HC-111: 44.7%

_____ Update or Verify SEG specific Control Board Placards:

___ 1. CVCS panel placard:

a. RCS boron - 102 ppm.

b. RCS H2 - 45 cc/kg.

c. Turbine Reference Value and Mode - matched with DEHC.

___ 2. Shift Reactivity Guidance placard:

a. BA: 0.3 gallons

b. RMU: 67 gallons

c. Dilutions: 20 gal RMU, 1-2 times per shift

___ 3. EAL Classification Placard CLEANED and placed on side of SS desk.

___ 4. LCO Timer CLEANED.

_____ SEG specific Magnetic Placards in place:

___1. NONE

_____ SEG specific or Protected Equipment Pink Status Control Tags in place:

___1. CS-46425, 12 MD AFWP

_____ SEG specific or Out of Service Yellow Caution Tags are in place:

___ 1. CS-46424, 11 TD AFWP ___ 4. CS-46314, 11 TD AFWP TO 11 STM GEN

___ 2. CS-46127, 11 MAIN STM TO 11 TD AFWP MV-32238 MV-32016 ___ 5. CS-46315, 11 TD AFWP TO 12 STM GEN

___ 3. CS-46128, 12 MAIN STM TO 11 TD AFWP MV-32239 MV-32017 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 20 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Pre-Scenario Checklist continued:

_____ ERCS driven recorders are on-scale (RCS temperature scaled 555º F to 565º F).

_____ ERCS alarm screen operating and alarms reset.

All ERCS terminals operating and set as follows:

CONF VARS R02 Alarm Summary Page CONE1 Group OP31_U1 R03 AFD CONC SAS (XS11) R04 TPM CONG1 Group QP CCDATA R05 QP LOADFOLL ERCS-R01 Group RADMON_U1 R06 Alarm Summary Page

_____ ERCS single point displays:

CONB 1T0499A 1U1613A CONE2 1Q0340A 1V4501A

_____ ERCS TPM set (Calorimetric - Auto Scaling - VENT).

_____ Set Turbine Control HMI Displays as follows:

___ 1. U1 E-H Turb Cont STA 2 (48087) to Control Valve Overview

___ 2. U1 Turb Aux Cont (48088) to Turb Overview

___ 3. U1 E-H Turb Cont STA 1 (48086) to Off Line Control

___ 4. DEHC alarms cleared.

_____ Verify DEHC VPL set ~0.1 to 0.3 above current valve position (not on limiter).

_____ YELLOW turnover sheets 1-9 available.

_____ Electronic PINGP 577 forms and TABS closed on both LAN connected PCs.

_____ Board-mounted EAL Tables are cleaned.

_____ Headsets turned on as necessary.

_____ Perform one of the following:

Clear web browser history and recent procedures in pdf.

Complete post-scenario checklist.

_____ Procedure checklist completed. See following page.

_____ Peer Check performed for simulator setup.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 21 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 PROCEDURE CHECKLIST:

NOTE: The following procedures will be used during this session. Verify the procedures are free of place keeping marks before starting the session and after the session are complete.

Before After 1st / 2nd 1st / 2nd

/ / 1C1.4 AOP1, RAPID POWER REDUCTION - UNIT 1

/ / 1C23, UNIT 1 TURBINE CONTROL SYSTEM

/ / 1C23 AOP 2, MALFUNCTION OF TURBINE EH CONTROL SYSTEM

/ / 1C51.3, 1P-431 PRESSURIZER PRESSURE - LOW

/ / C47012-0108, PRZR LO PRESS SI CHANNEL ALERT

/ / C47024-1203, D1 EMERGENCY GENERATOR LOCAL ALARM

/ / 1E-0, REACTOR TRIP OR SAFETY INJECTION

/ / 1ECA-0.0, LOSS OF ALL SAFEGUARDS AC POWER

/ / 1ES-0.1, REACTOR TRIP RECOVERY

/ / 1E-CAS, UNIT 1 CONTINUOUS ACTION & INFO PAGE

SUMMARY

/ / EAL Board

/ / 1FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK

/ / LAMINATE COPY OF 1C5, SECTION 5.5

/ / LAMINATE COPY OF 1C12.5, SECTIONS 5.8, 5.9, & 5.10

/ / REACTIVITY BRIEFING SHEET - MOC

/ / SWI O-28, NOTIFICATION OF OPS MNGR & NRC RESIDENT INSPECTOR

/ / T.S. LCO 3.3.1

/ / T.S. LCO BASES 3.3.1

/ / T.S. LCO 3.3.2

/ / T.S. LCO BASES 3.3.2

/ / T.S. LCO 3.8.1

/ / T.S. LCO 3.8.1 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 22 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Post-Scenario Checklist

_____ Clear web browser history and recent procedures in pdf.

_____ Computer generated PINGP 577 cleared.

_____ Procedure checklist completed. See previous page.

_____ Remove Pink Status Control Tags from the following equipment:

___ 1. CS-46425, 12 MD AFWP

_____ Magnetic placards removed:

___ 1. NONE

_____ Remove Yellow Caution Tags from the following equipment:

___ 1. CS-46424, 11 TD AFWP

___ 2. CS-46127, 11 MAIN STM TO 11 TD AFWP MV-32016

___ 3. CS-46128, 12 MAIN STM TO 11 TD AFWP MV-32017

___ 4. CS-46314, 11 TD AFWP TO 11 STM GEN MV-32238

___ 5. CS-46315, 11 TD AFWP TO 12 STM GEN MV-32239

_____ Board-mounted EAL Table is cleaned.

_____ All books, note pads, and calculators put away.

End Of Day Checklist

_____ Signs/placards removed and put away unless normal simulator configuration.

_____ If desired, floor PCs logged off if simulator will not be used again that day.

_____ Instructor station returned to normal with all books, paper, and etc. put away.

_____ Headsets turned off and put away if simulator will not be used again that day.

_____ Simulator reset to IC-10 unless another IC will be used for further training.

_____ Simulator placed in DORT if simulator will not be used again that day.

_____ Verify the following placards are erased:

CVCS panel

Shift Reactivity Guidance

LCO Timer

NRC Authentication Code Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 23 of 27 RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: 8/18/2020 DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS

1. 11 TD AFW PUMP is Out of Service for corrective maintenance.

T.S. LCO 3.7.5 Condition B has been entered with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months remaining.

11 TD AFW Pump is expected to be returned to service in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

PROTECTED EQUIPMENT 12 MD AFW PUMP SFP COOLING RAD MONITORS OOS ANNUNCIATORS OOS NONE NONE OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS NONE NONE OTHER EQUIPMENT OOS / STATUS Exposure: EOC Pressure: 2235 PSIG Unit 2 is at 100% power.

Power: 100% Xenon: Equilibrium Boron (CB): 102 PPM Rods: CBD @ 218 TAVG: 560°F Generator: 582 MW MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE NONE OPERATIONAL PLANS FOR COMING SHIFT

Prior to entering the simulator, perform a Pre-Job Brief for the following:

o Swap EH oil pumps per 1C23.

After taking the duty, swap running EH oil pumps per 1C23 and pre-job brief.

NEW PROCEDURES / INSTRUCTIONS of 9 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 4 (FP-T-SAT-75) Page 24 of 27 PI-ILT-NRC-2002S, 2020 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.